Analysis on special two-phase flow instabilities at full power natural circulation reactor condition
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Y. J. Zhang
Abstract
The experiments were performed on the test loop HRTL-5, which simulates the geometry and system design of the 5 MW nuclear heating reactor. In a wide range of inlet sub-cooling various flow instabilities were observed at p = 0.1 MPa and p = 1.5 MPa. Because of the different geometry design and operating conditions between the heating reactors and the boiling water reactors, the flow behavior presents great difference. Analysis shows: (1) under heating reactor conditions, sub-cooled boiling, condensation and void flashing are the fundamental thermodynamic processes; (2) sub-cooled boiling, condensation, void flashing and the compressibility of the steam space play an important role in the flow instabilities of the natural circulation system; (3) sub-cooled boiling instability, flashing instability, and flow excursion are the special instabilities at nuclear heating reactor conditions.
Kurzfassung
Die Experimente wurden durchgeführt an der Testanlage HRTL-5, die die Geometrie und den Systemaufbau des 5 MW Heizreaktors simuliert. Über einen weiten Bereich der Eintrittsunterkühlung wurden verschiedene Strömungsinstabilitäten bei p = 0.1 MPa undp = 1.5 MPa beobachtet. Wegen der Unterschiede im geometrischen Aufbau und bei den Betriebsbedingungen zwischen Heizreaktoren und Siedewasserreaktoren ist das Strömungsverhalten sehr unterschiedlich. Die Analyse zeigt: (1) unter Heizreaktorbedingungen sind unterkühltes Blasensieden, Kondensation, und Blasenverdampfung die fundamentalen thermodynamischen Prozesse; (2) unterkühltes Blasensieden, Kondensation, Blasenverdampfung sowie die Kompressibilität des Dampfraumes spielen eine wichtige Rolle bei den Strömungsinstabilitäten des Reaktors mit Naturumlauf system; (3) Instabilitäten durch unterkühltes Blasensieden, Blasenverdampfung und Strömungsexkursion sind Spezialfälle unter Heizreaktorbedingungen.
References
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© 2004, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Investigation on bifurcation characteristics of a natural circulation system with low steam quality and low pressur
- Analysis on special two-phase flow instabilities at full power natural circulation reactor condition
- Analysis of a total loss of pool water accident in MTR-type research reactors
- Calculation of control plates life time and worth at the ETRR-2 research reactor
- Nitrogen transport in the primary circuit of a VVER during a LOCA occurring under plant cool-down conditions
- Optimisation of occupational exposures during site remediation at WISMU
- Practical applications of the exemption principle in radiation protection
- Technical Note
- Determination of the replacement cooling tower capability at the ETRR-2 research reactor
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Investigation on bifurcation characteristics of a natural circulation system with low steam quality and low pressur
- Analysis on special two-phase flow instabilities at full power natural circulation reactor condition
- Analysis of a total loss of pool water accident in MTR-type research reactors
- Calculation of control plates life time and worth at the ETRR-2 research reactor
- Nitrogen transport in the primary circuit of a VVER during a LOCA occurring under plant cool-down conditions
- Optimisation of occupational exposures during site remediation at WISMU
- Practical applications of the exemption principle in radiation protection
- Technical Note
- Determination of the replacement cooling tower capability at the ETRR-2 research reactor
